【作者】 唐琦琳；

【导师】 王经；

【作者基本信息】 上海交通大学 ， 工程热物理， 2007， 硕士

【摘要】 蒸汽发生器(Steam Generator简称SG),作为核动力装置中一、二回路之间的连接枢纽,是核电站的关键设备,也是核动力装置运行中发生故障最多的设备之一。它的可靠性对核电厂的安全经济运行影响极大。提高蒸发器的安全可靠性和经济性,成为我国发展核电的关键技术和最迫切的任务之一。目前国内外学者对蒸发器内沸腾换热特性和流动特性进行了大量实验研究和理论研究,所得到的沸腾换热特性和流动特性的计算式与他们的实验条件密切相关。同时参考文献表明,对蒸发器二回路管束间汽液两相流流型变化特性以及流型变化对沸腾换热特性和流动特性影响的研究还不够充分,需要深入进行。基于上述研究背景,本文针对蒸发器内二回路的汽液两相流动是在管束间的狭窄通道内垂直向上进行的特点,提出了对蒸汽发生器二回路传热管束间狭窄通道的两相流沸腾传热和流动特性进行实验研究的目的。在课题组前人研究的基础上,本文研究主要为实验研究,搭建了管束外垂直向上狭窄通道流动沸腾实验台,进行了管束外狭窄通道内R113沸腾换热及两相流动特性的多次实验,对下述内容进行研究分析:(1)对管束外狭窄通道内流动沸腾过程中的两相流流型特征及过渡规律更多还原

【Abstract】 Steam Generator, as the hinge linking the primary and secondary circuits in nuclear-power device, is one of the easing-broken devices. Its reliability makes great effect on the security and economy of the nuclear power station. So enhancing the security and economy of Steam Generator is one of key techniques and urgent tasks for developing national nuclear power. Much effort has been given to the research about boiling heat transfer and hydraulics in Steam Generator, and the correlations are based on limited sets of data collected for specific experimental conditions. Major factors hindering modeling attempts include the inadequate representation of the flow patterns of two-phase flow in tube-bundle and an inability to determine the effect of varying flow patterns on the characteristic of boiling heat transfer and hydraulics. Based on aforementioned background, research is carried out to investigate the flow boiling heat transfer in tube-bundle complex narrow channel of the secondary circuit of Steam Generator.On the basis of previous studies of our group, work has been conducted on the experimental platform which makes up of a vertical tube-bundle narrow channel. Along this special channel, the boiling and flow characteristic of R113 have been carefully investigated. The major content is listed below:(1) By the experimental observation, four flow patterns have been observed in tube-bundle narrow channel: bubble, slug, churn and annular flow. In some更多还原